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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1164-1174
Technical Paper | doi.org/10.1080/00295450.2019.1607136
Articles are hosted by Taylor and Francis Online.
This paper describes evaluation results of thermophysical properties of stainless steel (SS) containing 5 mass % boron carbide (B4C) in its solid phase. First, the authors synthesized SS-B4C samples with emphasis on 5 mass % B4C and SS using a hot press method and then evaluated its homogeneity in several ways, such as chemical composition analysis, metallographic structure observation, and micro X-ray diffraction. This study also evaluated the density and the specific heat and thermal conductivity of the SS-B4C sample and found that the density becomes lower and the temperature dependence of the density decreased as the temperature rose compared to that of stainless steel Type 316L (SS316L) used as a reactor material. The specific heat became slightly higher than that of SS316L and showed similar temperature dependence up to 1073 K. Unexpectedly, the thermal conductivity became lower than that of SS316L and showed similar temperature dependence up to 1273 K.